RNP-RA/08-0016, Supplement to the Request for Administrative Changes to the Technical Specifications

Supplement to the Request for Administrative Changes to the Technical Specifications

ML080380327
Person / Time
Site:	Robinson
Issue date:	02/04/2008
From:	Baucom C Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/08-0016
Download: ML080380327 (7)

Text

10 CFR 50.90 Progress Energy Serial: RNP-RA/08-0016 FEB 0 4 2008 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 SUPPLEMENT TO THE REQUEST FOR ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS Ladies and Gentlemen:

In a letter dated November 19, 2007, Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. (PEC); submitted a request for an amendment to the Technical Specifications (TS) contained in Appendix A of the Operating License for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No. 2.

The letter proposed administrative changes to ensure that the TS are accurate. The proposed changes are under review by the NRC staff. An additional administrative change necessary to ensure the accuracy of the TS has been recently identified. Specifically, Section 5.6.6, "Post Accident Monitoring (PAM) Instrumentation Report," refers to Condition H of Limiting Condition for Operation (LCO) 3.3.3. The reference to Condition H should have been changed to Condition G with the renumbering of LCO 3.3.3 conditions approved in License Amendment No. 216 (NRC letter dated July 16, 2007). It is requested that this change be included with the previously requested changes.

Consistent with the other changes requested in the November 19, 2007, letter, this change is administrative and is intended to ensure the accuracy of the TS. This change involves the correction of the reference to Condition G instead of Condition H. There will be no changes to the plant design or to the procedural controls for the operation, surveillance, or maintenance of the plant. Therefore, the No Significant Hazards Consideration Determination and the Environmental Impact Consideration provided in the November 19, 2007, letter remain valid.

Attachment I provides an Affirmation as required by 10 CFR 50.30(b).

Attachment II provides a markup of the affected TS page. Attachment III provides the retyped TS page.

Progress Energy Carolinas, Inc.

Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550

United States Nuclear Regulatory Commission Serial: RNP-RA/08-0016 Page 2 of 2 In accordance with 10 CFR 50.91(b), Progress Energy Carolinas, Inc., is providing the State of South Carolina with a copy of this license amendment request.

If you have any questions concerning this matter, please contact me at (843) 857-1253.

Sincerely, C. T. Baucom Manager - Support Services - Nuclear Attachments:

I. Affirmation II. Markup of Technical Specifications Page III. Retyped Technical Specifications Page RAC/rac c: S. E. Jenkins, Manager, Infectious and Radioactive Waste Management Section (SC)

A. Gantt, Chief, Bureau of Radiological Health (SC)

V. M. McCree, NRC, Region II M. G. Vaaler, NRC Project Manager, NRR NRC Resident Inspector, HBRSEP Attorney General (SC)

United States Nuclear Regulatory Commission Attachment I to Serial: RNP-RA/08-0016 Page 1 of 1 AFFIRMATION The information contained in letter RNP-RA/08-0016 is true and correct to the best of my information, knowledge; and belief; and the sources of my information are officers, employees, contractors, and agents of Carolina Power and Light Company, also known as Progress Energy Carolinas, Inc. I declare under penalty of perjury that the foregoing is true and correct.

Executed On: ),/

T. D. Walt Vice President, HBRSEP, Unit No. 2

United States Nuclear Regulatory Commission Attachment II to Serial: RNP-RA/08-0016 2 Pages (including cover page)

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 SUPPLEMENT TO THE REQUEST FOR ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS MARKUP OF TECHNICAL SPECIFICATIONS PAGE

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

19. EMF-92-081(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," approved version as specified in the COLR.

20. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

approved version as specified in the COLR.

21. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," approved version as specified in the COLR.

22. EMF-96-029(P)(A), "Reactor Analysis System for PWRs,"

approved version as specified in the COLR.

23. EMF-92-116, "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.

24. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

25. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by Condition B or 14G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a-report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

(continued)

HBRSEP Unit No. 2 5.0-27 Amendment No. 244 1

United States Nuclear Regulatory Commission Attachment III to Serial: RNP-RA/08-0016 2 Pages (including cover page)

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 SUPPLEMENT TO THE REQUEST FOR ADMINISTRATIVE CHANGES TO THE TECHNICAL SPECIFICATIONS RETYPED TECHNICAL SPECIFICATIONS PAGE

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

19. EMF-92-081(A), "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors," approved version as specified in the COLR.

20. EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

approved version as specified in the COLR.

21. XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," approved version as specified in the COLR.

22. EMF-96-029(P)(A), "Reactor Analysis System for PWRs,"

approved version as specified in the COLR.

23. EMF-92-116, "Generic Mechanical Design Criteria for PWR Fuel Designs," approved version as specified in the COLR.

24. EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

25. EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," approved version as specified in the COLR.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by Condition B or G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

(continued)

HBRSEP Unit No. 2 5.0-27 Amendment No.